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Title: Development of structural design criteria for ITER.

Abstract

The irradiation environment experienced by the in-vessel components of fusion reactors such as HER presents structural design challenges not envisioned in the development of existing structural design criteria such as the ASME Code or RCC-MR. From the standpoint of design criteria, the most significant issues stem from the irradiation-induced changes in material properties, specifically the reduction of ductility, strain hardening capability, and fracture toughness with neutron irradiation. Recently, Draft 7 of the interim ITER structural design criteria (ISDC), which provide new rules for guarding against such problems, was released for trial use by the ITER designers. The new rules, which were derived from a simple model based on the concept of elastic follow up factor, provide primary and secondary stress limits as functions of uniform elongation and ductility. The implication of these rules on the allowable surface heat flux on typical first walls made of type 316 stainless steel and vanadium alloys are discussed.

Authors:
Publication Date:
Research Org.:
Argonne National Lab., IL (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
10649
Report Number(s):
ANL/TD/CP-95666
TRN: AH200127%%379
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Conference
Resource Relation:
Conference: 13th Topical Meeting on the Technology of Fusion Energy, Nashville, TN (US), 06/07/1998--06/11/1998; Other Information: PBD: 22 Jun 1998
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; DESIGN; FIRST WALL; FRACTURE PROPERTIES; HEAT FLUX; STAINLESS STEELS; STRAIN HARDENING; THERMONUCLEAR REACTORS; VANADIUM ALLOYS

Citation Formats

Majumdar, S. Development of structural design criteria for ITER.. United States: N. p., 1998. Web.
Majumdar, S. Development of structural design criteria for ITER.. United States.
Majumdar, S. 1998. "Development of structural design criteria for ITER.". United States. https://www.osti.gov/servlets/purl/10649.
@article{osti_10649,
title = {Development of structural design criteria for ITER.},
author = {Majumdar, S},
abstractNote = {The irradiation environment experienced by the in-vessel components of fusion reactors such as HER presents structural design challenges not envisioned in the development of existing structural design criteria such as the ASME Code or RCC-MR. From the standpoint of design criteria, the most significant issues stem from the irradiation-induced changes in material properties, specifically the reduction of ductility, strain hardening capability, and fracture toughness with neutron irradiation. Recently, Draft 7 of the interim ITER structural design criteria (ISDC), which provide new rules for guarding against such problems, was released for trial use by the ITER designers. The new rules, which were derived from a simple model based on the concept of elastic follow up factor, provide primary and secondary stress limits as functions of uniform elongation and ductility. The implication of these rules on the allowable surface heat flux on typical first walls made of type 316 stainless steel and vanadium alloys are discussed.},
doi = {},
url = {https://www.osti.gov/biblio/10649}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jun 22 00:00:00 EDT 1998},
month = {Mon Jun 22 00:00:00 EDT 1998}
}

Conference:
Other availability
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